On the possibility of twisted tubes assemblies application in steam generating systems of transport nuclear power installations

Аuthors

Mitrofanova O. V.^{1, 2*}, Ivlev O. A.¹, Fedorinov A. V.^{1, 2}

1. ,
2. National Research Nuclear University MEPhI (Moscow Engineering Physics Institute), 31, Kashirskoe shosse, Moscow, 115409, Russia

*e-mail: omitr@yandex.ru

Abstract

Computational analysis proposed in the present work is aimed at heat exchange intensification problems solution, thermal and hydraulic efficiency and reliability enhancement of nuclear pow er installations. The article considers the possibilities of twisted tube assemblies application in in ternal devices of steam‑generating systems as part of transport nuclear power plants with water‑water reactors under pressure. Verification of the computational algorithm based on comparison with experimental data was performed, and analysis of the impact of the passage section geometry and screw‑shaped channels twist step on the degree of heat transfer intensification was presented. The performed studies allow extending significantly the application scope of heat exchange channels with twisted tubes in other heat exchange devices with different media employed in systems, comprising the transport nuclear power installations.

Keywords:

vortex flow, the steam generating unit, thermal power efficiency, helicity, vorticity, heat transfer enhancement

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